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| Home > Publications database > Innovative approach for sustainable and low-waste production of99Mo-based radiodiagnostics using accelerator-based neutron source |
| Poster (Invited) | FZJ-2024-03632 |
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2024
Abstract: Nuclear medicine diagnostics that are integral to modern healthcare, heavily rely on the radionuclide99Mo, traditionally produced in nuclear reactors through the fission of 235U [1, 2,3]. However, the complex radiochemical processing involved generates substantial radioactivewaste, necessitating a shift towards more sustainable practices. This poster presents the99Mo Best joint project, an initiative focused on developing an innovative, cost-efficient conceptfor the production and utilization of 99Mo-based radiodiagnostics, utilizing the 98Mo(n,γ)99Mo reaction eliminating fissile materials and minimizing radioactive waste.The project comprises three key sub-projects:1. Process Optimization: This involves refining the processes for generating 99Mo-basedradiodiagnostics, as well as improving their processing and utilization in clinical settings.2. Neutron Target Technology: Developing high neutron flux density neutron target technologyis crucial for irradiation with reduced radiation doses, ensuring safe handling andprocessing of Mo samples post-irradiation.3. Radiation Protection and Disposal: Addressing safety concerns, this sub-project aims todetermine radiation protection and disposal issues pertinent to the novel 99Mo productionprocess, ensuring a secure and sustainable approach.This comprehensive approach aims to create a paradigm shift in the field of nuclear medicineby offering a sustainable and efficient alternative to traditional 99Mo production methods,mitigating environmental impact and advancing the application of accelerator-based neutronradiation sources in medical radioisotope production.AcknowledmentsThis work is supported by the German Federal Ministry of Education and Research (BMBF) underGrant No. 02NUK080B.References1. NEA (2019), “The Supply of Medical Radioisotopes: 2019 Medical Isotope Demand and Capacity2. Projection for the 2019–2024 Period”, OECD Publishing, Paris.3. Deutscher Bundestag, Drucksache 17/3142, 2010.4. Jaroszewicz J, Marcinkowska Z, Pytel K (2014) Production of fission product 99Mo using highenricheduranium plates in Polish nuclear research reactor MARIA: Technology and neutronicanalysis. Nukleonika 59(2):43–52.
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